Tritium Fuel Cycle: Challenges and Advances for Fusion Power Plants

Remi Delaporte-Mathurin

Postdoctoral Researcher
Plasma Science and Fusion Center
Massachusetts Institute of Technology

Seminar Information

Seminar Series
Energy: Joint Mechanical & Aerospace Engineering Dept & Center for Energy Research

Seminar Date - Time
January 29, 2025, 11:00 am
-
12:00

Seminar Location
Online ONLY via Zoom (connection in link below)

Seminar Recording Available: Please contact seminar coordinator, Jake Blair at (j1blair@ucsd.edu)

Remi Delaporte-Mathurin

Abstract

The tritium fuel cycle presents one of the most critical challenges for achieving sustainable fusion power. Tritium, a key fuel for fusion reactions, is both scarce and radioactive, requiring efficient production, handling, and recycling to support the operation of future fusion power plants. This seminar will explore the scientific and engineering hurdles associated with the tritium fuel cycle, including production, transport, storage, and recovery, as well as the stringent safety and environmental considerations.

We will highlight ongoing research at the Plasma Science and Fusion Center (PSFC) aimed at addressing these challenges, with a focus on the development of tritium breeding blankets. These blankets are designed to produce tritium in situ by leveraging neutron interactions with lithium-containing materials. Our work includes experimental investigations, such as the LIBRA project, and advanced modeling efforts using the open-source hydrogen transport code FESTIM. Key topics will include the optimisation of tritium production and recovery, the role of material selection, and the integration of tritium systems with fusion reactor designs. By advancing these technologies, we aim to pave the way toward achieving tritium self-sufficiency, a cornerstone of viable fusion energy systems.

Speaker Bio

Dr. Delaporte-Mathurin started his career in fusion at the Culham Science Centre for Fusion Energy (UKAEA), did his Ph.D. at the french Institute for Magnetic Fusion Research (CEA) and recently joined the Plasma Science and Fusion Center at Massachusetts Institute of Technology (MIT) as a postdoc associate. His primary research focus is hydrogen transport modelling fusion in relevant materials. He is the lead developer of the FESTIM code opens in new tab/window. His Ph.D. project investigated tritium retention in the ITER divertor but his current focus is now on tritium breeding technologies through the project LIBRA. Aside from his core research, Dr. Delaporte-Mathurin has a keen interest in data visualisation and popularisation of science.